ML062990261: Difference between revisions

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| number = ML062990261
| number = ML062990261
| issue date = 10/17/2006
| issue date = 10/17/2006
| title = Seabrook Station, Unit 1 - Tech Spec Pages for Amendment 113 Removal of License Condition 2.G
| title = Tech Spec Pages for Amendment 113 Removal of License Condition 2.G
| author name =  
| author name =  
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-2
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-2

Revision as of 16:10, 10 February 2019

Tech Spec Pages for Amendment 113 Removal of License Condition 2.G
ML062990261
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 10/17/2006
From:
NRC/NRR/ADRO/DORL/LPLI-2
To:
Miller G, NRR/DLPM, 415-2481
Shared Package
ML061880002 List:
References
TAC MD0697
Download: ML062990261 (2)


Text

-6-F. Fire Protection FPL Energy Seabrook, LLC, shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, the Fire Protection Program Report, and the Fire Protection of Safe Shutdown Capability Report for the facility, as supplemented and amended, and as approved in the Safety Evaluation Report, dated March 1983; Supplement 4, dated May 1986; Supplement 5, dated July 1986;Supplement 6, dated October 1986; Supplement 7, dated October 1987;and Supplement 8, dated May 1989 subject to the following provisions:

FPL Energy Seabrook, LLC, may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain shutdown in the event of a fire.G. DELETED H. Financial Protection The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.DELETED AMENDMENT NO. 86, 113 INDEX 6.0 A SECTION 6.4 DMINISTRATIVE CONTROLS PAGE 6-4 (THIS SPECIFICATION NUMBER IS NOT USED)I ...............................

6.5 (THIS SPECIFICATION NUMBER IS NOT USED) ...................

6.6 SAFETY

LIMIT VIOLATION 6.7 PROCEDURES AND PROGRAMS 6.8 REPORTING REQUIREMENTS

6.8.1 ROUTINE

REPORTS.........................................

Startup R eport ...........................................................................................................

A nnual R eports .....................................................................................................

.....Annual Radiological Environmental Operating Report .........................................

Annual Radioactive Effluent Release Report ........................................................

CORE OPERATING LIMITS REPORT............................

6.8.2 SPECIAL

REPORTS...........................................

6-4 6-4 6-5 I 6-11 6-11 6-12 6-13 6-13 6-14 6-19 SEABROOK -UNIT 1 xiv Amendment No. 34, 67, 73, 88, 104, 109 113 ADMINISTRATIVE CONTROLS 6.2.3 (THIS SPECIFICATION NUMBER IS NOT USED)6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Control Room Commander in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the station.6.3 (THIS SPECIFICATION NUMBER IS NOT USED)6.4 (THIS SPECIFICATION NUMBER IS NOT USED)6.5 (THIS SPECIFICATION NUMBER IS NOT USED)6.6 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated: a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Site Vice President and the CNRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />;b. A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the SORC. This report shall describe:

(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence;

c. The Safety Limit Violation Report shall be submitted to the Commission, the CNRB, and the Site Vice President within 14 days of the violation; and d. Operation of the station shall not be resumed until authorized by the Commission.

SEABROOK -UNIT I 6-4 Amendment No. 55, 04,113